|
|---|
Category:MEETING MINUTES & NOTES--CORRESPONDENCE
MONTHYEARML20210H6681999-07-29029 July 1999
Summary of 990329 Meeting with Gpu in Forked River,Nj Re Possibility of Decommisssioning of Oyster Creek Nuclear Generating Station.List of Attendees & Licensee Handouts Provided
ML20195G1391998-11-16016 November 1998
Summary of 981103 Meeting with Gpu in Rockville,Md Re Possible Shutdown & Decommissioning of Oyster Creek Nuclear Generating Station in Year 2000.List of Attendees & Handout Encl
ML20216E3421997-09-0303 September 1997
Summary of 970826 Meeting W/Gpu in Rockville,Md Re Possibility of Decommissioning of Plant.Agenda,Meeting Handouts & Primarily Centered Activities Associated W/Decommissioning Plant in Yr 2000 Encl
ML20148D8531997-05-28028 May 1997
Summary of 970502 Meeting W/Util to Discuss Status of Implementation Schedule for Completion of Installation of Thermo-lag at Plants.List of Attendees Encl
ML20149J5251994-12-29029 December 1994
Summary of 941219 Meeting W/Util Re Status of Licensing Actions.List of Attendees & Activities Encl
ML20058K1831993-11-26026 November 1993
Summary of 931119 Meeting W/Licensee in Rockville,Md Re Licensing Issues Involved in Construction & Loading of Independent Spent Fuel Storage Installation to Be Constructed at Plant
ML20059F3931993-10-27027 October 1993
Summary of 931020 Meeting W/Gpu Nuclear Corp in Rockville,Md Re Status of Plant Licensing Actions.List of Attendees Encl
ML20128K8261993-02-0909 February 1993
Summary of 921123-24 Meeting in King of Prussia,Pa Re Region I Positions on Operator Licensing Issues & Solicit Input from Util Training Staffs
ML20127M5941993-01-26026 January 1993
Summary of 930112 Meeting W/Util in Rockville,Md Re Reactor Bldg Access Control Mod & Operational Safeguards Response Evaluation.List of Attendees & Handouts Encl
ML20127F6681993-01-14014 January 1993
Summary of 930112 Meeting W/Util in Rockville,Md Re Status of Licensing Actions.List of Individuals Participating in Discussion & Marked Up Copy of Staff Pmr Encl
ML20127E1281993-01-13013 January 1993
Summary of 930106 Meeting W/Util in Rockville,Md Re Insp of Plant Core Spray Spargers.List of Discussion Participants & Licensee Agenda Encl
ML20125C2461992-12-0707 December 1992
Summary of 921118 Meeting W/Util in Rockville,Md Re Status of Licensing Actions
ML20058K1871990-12-11011 December 1990
Summary of 901114 Progress Review Meeting at Plant Site Re Status of Licensing Actions.List of Attendees Encl
ML20062F1121990-11-15015 November 1990
Summary of 901107 Meeting W/Util in Rockville,Md,Re Fuel Channel Bowing & Reuse of Fuel Channels at Facility
ML20059N5951990-10-0303 October 1990
Summary of 900919 Meeting W/Util in Rockville,Md to Discuss Matters Re Plant Drywell Corrosion.Viewgraphs Encl
ML20246M5871989-08-29029 August 1989
Summary of 890802 Meeting W/Util in Rockville,Md Re full-term OL & Other Licensing Activities.List of Attendees & marked-up Regulatory Info Tracking Sys List of Unresolved SEP Topics & TAC Numbers Encl
ML20246L4001989-07-10010 July 1989
Summary of 890627 Meeting W/Util in Rockville,Md Re Combustible Gas Control for Plant.List of Individuals Attending Meeting,Proposed Meeting Agenda,Matl Used by Util in Discussion & Condensed History of Gas Control Issue Encl
ML20245J7191989-06-20020 June 1989
Summary of 890607 Meeting W/Util in Forked River,Nj to Discuss Status of Plant Licensing Actions.List of Attendees & marked-up Copy of Regulatory Info Tracking Sys Encl
ML20247K0901989-05-23023 May 1989
Summary of 890517 Meeting W/Inpo Re Similarities & Differences Between Performance Indicator Programs.Detailed Discussion Encl
ML20247K1011989-05-16016 May 1989
Summary of 890517 Meeting W/Inpo in Bethesda,Md Re Similarities & Differences Between INPO & NRC Performance Indicators
ML20245J0141989-04-26026 April 1989
Summary of 890413 Meeting W/Util in Rockville,Md Re Status of Licensing actions.Marked-up Regulatory Info Tracking Sys List Encl
ML20235N0661989-02-21021 February 1989
Summary of 890213 Meeting W/Util & State of Nj Re Air Sys Relating to MSIVs & Reactor Bldg to Torus Vacuum Breakers. Util Should Document Overall Methodology Used for MSIV Leakage Problems Prior to Startup.Viewgraphs Encl
ML20235H0521989-02-10010 February 1989
Summary of 890130 Meeting W/Util in Rockville,Md to Discuss SSOMI (SSOMI-design Phase) Issue 2 Re Setpoints for Process Variables & Actions to Be Taken Before Startup.List of Attendees & Agenda Encl
ML20195H9671988-11-23023 November 1988
Summary of 881110 Meeting W/Util in Rockville,Md Re Status of Facility Licensing Actions
ML20155F4801988-10-0606 October 1988
Summary of 880928 Progress Review Meeting W/Util in Forked River,Nj Re Status of Plant Licensing Actions
ML20207M0771988-10-0505 October 1988
Summary of Operating Reactors Events Meeting 88-39 on 881004.List of Attendees & Viewgraphs Encl
ML20154F7971988-09-15015 September 1988
Summary of 880901 QA Meeting W/Util in Rockville,Md to Discuss Rev 2 of Util Operational QA Plan for Plants.Agenda & List of Participants Encl
ML20207F4451988-08-0909 August 1988
Summary of 880721 Meeting W/Util in Rockville,Md Re Retran Analytical Model & Cycle 12 Fuel Reload Analyses.Attendance List & Matl Used by Licensee in Meeting Encl
ML20151L8991988-07-28028 July 1988
Summary of 880713 Progress Review Meeting W/Util in Rockville,Md Re Status of Licensing Actions.List of Participants & marked-up Copy of Staff Regulatory Info Tracking Sys Encl
ML20150B3271988-07-0606 July 1988
Summary of 880628 Meeting W/Util in Rockville,Md Re Facility Outage IGSCC Insp/Stress Improvement Plans
ML20150C0101988-06-22022 June 1988
Summary of 880525 Meeting W/Gpu in Rockville,Md Re Matters Related to site-specific Response Spectra.Viewgraphs Encl
ML20195K0451988-06-16016 June 1988
Summary of 880526 Meeting W/Util in Rockville,Md Re Matters on Oyster Creek-12R Outage 1GSCC Insp/Stress Improvement Plan as Described in Licensee Ltr .Inps/stress Improvement Plans Rept Encl
ML20154C6511988-05-0909 May 1988
Summary of 880414 Progress Review Meeting W/Util & State of Nj Re Status of Facility Licensing Actions.List of Attendees Encl
ML20196J9901988-03-0707 March 1988
Summary of 880224 Meeting W/Util in Rockville,Md Re Status of Plant Licensing Actions.List of attendees,marked-up Licensing Action Rept & Updated SEP Issues Encl
ML20149L5861988-02-16016 February 1988
Summary of 871221 Meeting W/Util in Bethesda,Md Re Licensee Proposed Methodology to Develop New Seismic Floor Response Spectra.Attendance List Encl
ML20149H8331988-02-10010 February 1988
Summary of 880106 Meeting W/Util & State of Nj in Bethesda,Md Re Status of Plant Licensing actions.Marked-up Licensing Action Rept,List of Attendees,Util Topical Rept on Fuel Reload Review & Cycle 12 Reload Schedule Encl
ML20236W3801987-11-30030 November 1987
Summary of 871113 Meeting W/Util in Bethesda,Md Re Drywell Corrosion Problem at Facility.List of Attendees,Proposed Meeting Agenda & Util Presentation Encl
ML20236P2841987-11-0505 November 1987
Summary of Operating Reactors Events Meeting 87-38 on 871103.List of Attendees,Viewgraphs & Summary of Reactor Scrams Encl
ML20235W9431987-10-13013 October 1987
Summary of Operating Reactors Events Meeting 87-32 on 870922.Notes That Meeting 87-31 Did Not Occur.List of Attendees & Events Discussed & Significant Elements of Events Encl
ML20239A6721987-09-11011 September 1987
Summary of 870903 Meeting W/Util in Bethesda,Md Re Util Proposed Methodology to Develop New Seismic Floor Response Spectra for Plant.List of Meeting Attendees & Viewgraphs Encl
ML20237K6461987-08-0606 August 1987
Summary of 870619 Meeting W/Util in King of Prussia,Pa Re Changes to Util Emergency Plan for Plants Based on Changing Plant Status & Reclassification to Post Defueling Monitored Storage
ML20235U3351987-07-14014 July 1987
Summary of 870707 Meeting W/Util in Bethesda,Md Re Proposed Methodology to Develop New Seismic Floor Response Spectra for Plant.List of Meeting Attendees & Licensee Agenda Encl
ML20215K0041987-06-18018 June 1987
Summary of 870611 Meeting W/Util in Bethesda,Md Re Drywell Corrosion at Plant & Status of Sep.Attendance List & Util Agenda for Proposed Actions Encl
ML20214L1171987-05-22022 May 1987
Summary of 870515 Meeting W/Util in Bethesda,Md Re Status of Station Licensing Actions.Attendance List & marked-up Licensing Action Rept Encl
ML20207A5221987-05-15015 May 1987
Summary of Operating Reactors Event Meeting 87-13 on 870507 Re Events Which Occurred Since 870428.List of Attendees, Events Discussed & Significant Elements of Events & Summary of Events Presented Encl
ML20207S3431987-03-13013 March 1987
Summary of 870226 Meeting W/Util in Bethesda,Md Re Plans to Mitigate Corrosion of Drywell Shell.List of Attendees & Meeting Agenda Encl
ML20207S1651987-03-13013 March 1987
Summary of 870120 Meeting W/Bwr Owners Group in Bethesda,Md Re Sys for Combustible Gas Control During Loca.Viewgraphs & Attendees List Encl
ML20207R9701987-03-0909 March 1987
Summary of 870211 Meeting W/Util in Bethesda,Md Re Conceptual Design of Isolation Condensers Drywell Piping Penetrations.Attendee List Encl
ML20207Q0871987-01-14014 January 1987
Summary of 861219 Third Meeting W/Util in Bethesda,Md Re Corrosion of Outer Drywell Shell at Elevation Just Below Downcomers.Supporting Documentation Encl
ML20207N2271987-01-0505 January 1987
Summary of 861210 Meeting W/Util,Niagara Mohawk Power Corp, GE & Chicago Bridge & Iron in Bethesda,Md Re Corrosion of Outer Surface of Drywell Shell.List of Attendees,Drywell Figures,Meeting Notice & Licensee Handout Encl
1999-07-29
[Table view]
Category:MEETING SUMMARIES-INTERNAL (NON-TRANSCRIPT)
MONTHYEARML20210H6681999-07-29029 July 1999
Summary of 990329 Meeting with Gpu in Forked River,Nj Re Possibility of Decommisssioning of Oyster Creek Nuclear Generating Station.List of Attendees & Licensee Handouts Provided
ML20195G1391998-11-16016 November 1998
Summary of 981103 Meeting with Gpu in Rockville,Md Re Possible Shutdown & Decommissioning of Oyster Creek Nuclear Generating Station in Year 2000.List of Attendees & Handout Encl
ML20216E3421997-09-0303 September 1997
Summary of 970826 Meeting W/Gpu in Rockville,Md Re Possibility of Decommissioning of Plant.Agenda,Meeting Handouts & Primarily Centered Activities Associated W/Decommissioning Plant in Yr 2000 Encl
ML20148D8531997-05-28028 May 1997
Summary of 970502 Meeting W/Util to Discuss Status of Implementation Schedule for Completion of Installation of Thermo-lag at Plants.List of Attendees Encl
ML20149J5251994-12-29029 December 1994
Summary of 941219 Meeting W/Util Re Status of Licensing Actions.List of Attendees & Activities Encl
ML20058K1831993-11-26026 November 1993
Summary of 931119 Meeting W/Licensee in Rockville,Md Re Licensing Issues Involved in Construction & Loading of Independent Spent Fuel Storage Installation to Be Constructed at Plant
ML20059F3931993-10-27027 October 1993
Summary of 931020 Meeting W/Gpu Nuclear Corp in Rockville,Md Re Status of Plant Licensing Actions.List of Attendees Encl
ML20128K8261993-02-0909 February 1993
Summary of 921123-24 Meeting in King of Prussia,Pa Re Region I Positions on Operator Licensing Issues & Solicit Input from Util Training Staffs
ML20127M5941993-01-26026 January 1993
Summary of 930112 Meeting W/Util in Rockville,Md Re Reactor Bldg Access Control Mod & Operational Safeguards Response Evaluation.List of Attendees & Handouts Encl
ML20127F6681993-01-14014 January 1993
Summary of 930112 Meeting W/Util in Rockville,Md Re Status of Licensing Actions.List of Individuals Participating in Discussion & Marked Up Copy of Staff Pmr Encl
ML20127E1281993-01-13013 January 1993
Summary of 930106 Meeting W/Util in Rockville,Md Re Insp of Plant Core Spray Spargers.List of Discussion Participants & Licensee Agenda Encl
ML20125C2461992-12-0707 December 1992
Summary of 921118 Meeting W/Util in Rockville,Md Re Status of Licensing Actions
ML20058K1871990-12-11011 December 1990
Summary of 901114 Progress Review Meeting at Plant Site Re Status of Licensing Actions.List of Attendees Encl
ML20062F1121990-11-15015 November 1990
Summary of 901107 Meeting W/Util in Rockville,Md,Re Fuel Channel Bowing & Reuse of Fuel Channels at Facility
ML20059N5951990-10-0303 October 1990
Summary of 900919 Meeting W/Util in Rockville,Md to Discuss Matters Re Plant Drywell Corrosion.Viewgraphs Encl
ML20246M5871989-08-29029 August 1989
Summary of 890802 Meeting W/Util in Rockville,Md Re full-term OL & Other Licensing Activities.List of Attendees & marked-up Regulatory Info Tracking Sys List of Unresolved SEP Topics & TAC Numbers Encl
ML20246L4001989-07-10010 July 1989
Summary of 890627 Meeting W/Util in Rockville,Md Re Combustible Gas Control for Plant.List of Individuals Attending Meeting,Proposed Meeting Agenda,Matl Used by Util in Discussion & Condensed History of Gas Control Issue Encl
ML20245J7191989-06-20020 June 1989
Summary of 890607 Meeting W/Util in Forked River,Nj to Discuss Status of Plant Licensing Actions.List of Attendees & marked-up Copy of Regulatory Info Tracking Sys Encl
ML20247K0901989-05-23023 May 1989
Summary of 890517 Meeting W/Inpo Re Similarities & Differences Between Performance Indicator Programs.Detailed Discussion Encl
ML20247K1011989-05-16016 May 1989
Summary of 890517 Meeting W/Inpo in Bethesda,Md Re Similarities & Differences Between INPO & NRC Performance Indicators
ML20245J0141989-04-26026 April 1989
Summary of 890413 Meeting W/Util in Rockville,Md Re Status of Licensing actions.Marked-up Regulatory Info Tracking Sys List Encl
ML20235N0661989-02-21021 February 1989
Summary of 890213 Meeting W/Util & State of Nj Re Air Sys Relating to MSIVs & Reactor Bldg to Torus Vacuum Breakers. Util Should Document Overall Methodology Used for MSIV Leakage Problems Prior to Startup.Viewgraphs Encl
ML20235H0521989-02-10010 February 1989
Summary of 890130 Meeting W/Util in Rockville,Md to Discuss SSOMI (SSOMI-design Phase) Issue 2 Re Setpoints for Process Variables & Actions to Be Taken Before Startup.List of Attendees & Agenda Encl
ML20195H9671988-11-23023 November 1988
Summary of 881110 Meeting W/Util in Rockville,Md Re Status of Facility Licensing Actions
ML20155F4801988-10-0606 October 1988
Summary of 880928 Progress Review Meeting W/Util in Forked River,Nj Re Status of Plant Licensing Actions
ML20207M0771988-10-0505 October 1988
Summary of Operating Reactors Events Meeting 88-39 on 881004.List of Attendees & Viewgraphs Encl
ML20154F7971988-09-15015 September 1988
Summary of 880901 QA Meeting W/Util in Rockville,Md to Discuss Rev 2 of Util Operational QA Plan for Plants.Agenda & List of Participants Encl
ML20207F4451988-08-0909 August 1988
Summary of 880721 Meeting W/Util in Rockville,Md Re Retran Analytical Model & Cycle 12 Fuel Reload Analyses.Attendance List & Matl Used by Licensee in Meeting Encl
ML20151L8991988-07-28028 July 1988
Summary of 880713 Progress Review Meeting W/Util in Rockville,Md Re Status of Licensing Actions.List of Participants & marked-up Copy of Staff Regulatory Info Tracking Sys Encl
ML20150B3271988-07-0606 July 1988
Summary of 880628 Meeting W/Util in Rockville,Md Re Facility Outage IGSCC Insp/Stress Improvement Plans
ML20150C0101988-06-22022 June 1988
Summary of 880525 Meeting W/Gpu in Rockville,Md Re Matters Related to site-specific Response Spectra.Viewgraphs Encl
ML20195K0451988-06-16016 June 1988
Summary of 880526 Meeting W/Util in Rockville,Md Re Matters on Oyster Creek-12R Outage 1GSCC Insp/Stress Improvement Plan as Described in Licensee Ltr .Inps/stress Improvement Plans Rept Encl
ML20154C6511988-05-0909 May 1988
Summary of 880414 Progress Review Meeting W/Util & State of Nj Re Status of Facility Licensing Actions.List of Attendees Encl
ML20196J9901988-03-0707 March 1988
Summary of 880224 Meeting W/Util in Rockville,Md Re Status of Plant Licensing Actions.List of attendees,marked-up Licensing Action Rept & Updated SEP Issues Encl
ML20149L5861988-02-16016 February 1988
Summary of 871221 Meeting W/Util in Bethesda,Md Re Licensee Proposed Methodology to Develop New Seismic Floor Response Spectra.Attendance List Encl
ML20149H8331988-02-10010 February 1988
Summary of 880106 Meeting W/Util & State of Nj in Bethesda,Md Re Status of Plant Licensing actions.Marked-up Licensing Action Rept,List of Attendees,Util Topical Rept on Fuel Reload Review & Cycle 12 Reload Schedule Encl
ML20236W3801987-11-30030 November 1987
Summary of 871113 Meeting W/Util in Bethesda,Md Re Drywell Corrosion Problem at Facility.List of Attendees,Proposed Meeting Agenda & Util Presentation Encl
ML20236P2841987-11-0505 November 1987
Summary of Operating Reactors Events Meeting 87-38 on 871103.List of Attendees,Viewgraphs & Summary of Reactor Scrams Encl
ML20235W9431987-10-13013 October 1987
Summary of Operating Reactors Events Meeting 87-32 on 870922.Notes That Meeting 87-31 Did Not Occur.List of Attendees & Events Discussed & Significant Elements of Events Encl
ML20239A6721987-09-11011 September 1987
Summary of 870903 Meeting W/Util in Bethesda,Md Re Util Proposed Methodology to Develop New Seismic Floor Response Spectra for Plant.List of Meeting Attendees & Viewgraphs Encl
ML20237K6461987-08-0606 August 1987
Summary of 870619 Meeting W/Util in King of Prussia,Pa Re Changes to Util Emergency Plan for Plants Based on Changing Plant Status & Reclassification to Post Defueling Monitored Storage
ML20235U3351987-07-14014 July 1987
Summary of 870707 Meeting W/Util in Bethesda,Md Re Proposed Methodology to Develop New Seismic Floor Response Spectra for Plant.List of Meeting Attendees & Licensee Agenda Encl
ML20215K0041987-06-18018 June 1987
Summary of 870611 Meeting W/Util in Bethesda,Md Re Drywell Corrosion at Plant & Status of Sep.Attendance List & Util Agenda for Proposed Actions Encl
ML20214L1171987-05-22022 May 1987
Summary of 870515 Meeting W/Util in Bethesda,Md Re Status of Station Licensing Actions.Attendance List & marked-up Licensing Action Rept Encl
ML20207A5221987-05-15015 May 1987
Summary of Operating Reactors Event Meeting 87-13 on 870507 Re Events Which Occurred Since 870428.List of Attendees, Events Discussed & Significant Elements of Events & Summary of Events Presented Encl
ML20207S1651987-03-13013 March 1987
Summary of 870120 Meeting W/Bwr Owners Group in Bethesda,Md Re Sys for Combustible Gas Control During Loca.Viewgraphs & Attendees List Encl
ML20207S3431987-03-13013 March 1987
Summary of 870226 Meeting W/Util in Bethesda,Md Re Plans to Mitigate Corrosion of Drywell Shell.List of Attendees & Meeting Agenda Encl
ML20207R9701987-03-0909 March 1987
Summary of 870211 Meeting W/Util in Bethesda,Md Re Conceptual Design of Isolation Condensers Drywell Piping Penetrations.Attendee List Encl
ML20207Q0871987-01-14014 January 1987
Summary of 861219 Third Meeting W/Util in Bethesda,Md Re Corrosion of Outer Drywell Shell at Elevation Just Below Downcomers.Supporting Documentation Encl
ML20207N2271987-01-0505 January 1987
Summary of 861210 Meeting W/Util,Niagara Mohawk Power Corp, GE & Chicago Bridge & Iron in Bethesda,Md Re Corrosion of Outer Surface of Drywell Shell.List of Attendees,Drywell Figures,Meeting Notice & Licensee Handout Encl
1999-07-29
[Table view] |
Text
. _ _ _ _ _ _ - _ _ _ _ - _ _ _ _ _ _ - _ _ _ _ -
DocJ<d
,pf'p eA,h UNITED STATES
- n NUCLEAR REGULATORY COMMISSION
{ j WASHING TON, D. C. 205b3 k....,/ January 13, 1993 Do ket No. 50-219 LICENSEE: GPU Nuclear Corporation FACILITY: Oyster Creek Nuclear Generating Station
SUBJECT:
SUMMARY
OF MEETING REGARDINr. INSFECTION OF OYSTER CREEK CORE SPRAY SPARGERS On Wednesday, January 6,1993, a meeting .vas held at One White flint North, Rockville, Maryland with GPU Nuclear Corporation (GPUN/ licensee) to discuss the inspection and testing of the downcomer to the core spray sparger No. 1.
During the testing the licensee found a small leak in one of the transition coupling welds (L-3A) of the downcomer. Enclosure 1 is the list of individuals participating in the discussion. Enclosure 2 is the licensee's agenda. The following is a summary of the significant items discussed.
The licensee presented a detailed description of the core spray sparger system and a past history of the results uf inspections and testing of the spargers since 1978 (see Section !!! of Enclosure 2).
The licensee indicated that during an air test of core spray sparger System No.1. the licensee detected a steady stream of air bubbles from the System 1 transition pipe coupling. A visual examination of the coupling indicated that there was a 1/8" diameter blow hole in weld (L-3A). They also stated that there was no sign of fatigue cracking or IGSCC and that there was no other indication detected in the remainder of the weld. Service loads are small.
The licensee also determined that the 1/8" blow hole defect in the 1/4" fillet weld is not a structural problem and that the blow hole leakage is 1 to 3 gpm l via the annulus. Even with this leakage there will still be a large flow margin above technical specification flow requirements.
Based on the above, the licensee concluded that in GPUN's best judgement the leak is due to a weld defect due to 20+ years of heatup and cooldown. They also concluded that a clamp over the joint is not needed and that they prefer not to install the clamp because of problems that could arise during l installation. They stated, however, that clamp, tooling design and l fabrication is ongoing.
As a result of the discussion, the staff advised GPUN that they should analyze the effects on the sparger system due to the limiting pipe break. The licensee should assure that under worst design conditions that failure of the core spray pipe coupling could not occur. The staff also requested that GPUN 1 r.O A 0 9 ju, ')
ue
GPU Nuclear Corporation !
review their inspection results of the defective weld and determine what percentage of the weld would be acceptable in accordance with the requirements of ASME Section XI. Based on the results of the analysis the staff will make ,
a determination whether the installation of the clamp is necessary.
Alexander W. Dromerick, Senior Project Manager l Project Directorate 1-4
~
DivisionofReactorProjects-I/II -
Of fice of Nuclear Reactor Regulation
Enclosures:
As stated cc w/ enclosures:
See next page Distribution:
Docket File i NRC & Local PDRs PD I-4 Memo TMurley/FMiraglia JPartlow '
SVarga JCalvo '
ADromerick SNorris OGC EJordan MBanic WKoo *
- JZimmerman i HShaw RMcBrearty MRazzaque RHermann.
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. VMcCree, EDO JFRogge, RI OH ICE L A: PDI .
PM;PDI-44 D:PD M NAME SYr E ebk:cn- J5tolzh D AT E --
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- 0FFICIAL RECORD LOPY -
Document Name: G:\DROMERIC\0CMG b
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Mr. John J. Barton Oyster Creek Nuclear GPU Nuclear Corporation Getierating Station cc:
Ernest L. Blake, Jr., Esq' fire Resident inspector Shaw, Pittman, Potts & Trowbridge c/o U.S. Nuclear Regulatory Commission 2300 N Street, NW. Post Office Box 445 Washington, DC 20037 Forked River, New Jersey 08731 Regional Administrator, Region I Kent Tosch, Chief U.S. Nuclear Regulatory Commission New Jersey Department of 475 Allendale Road Environmental Protection King of Prussia, Pennsylvania 19406 Bureau of Nuclear Engineering -
CN 415 BWR Licensing Manager Trenton, New Jersey 08625 GPU Nuclear Corporation 1 Upper Pond Road Parsippany, New Jersey 07054 Mayor lacey Township 818 West Lacey Road Forked River, New Jersey 08731 Licensing Manager Oyster Creek Nuclear Generating Station Mail Stop: Site Emergency Bldg.
Post Office Box 388 forked River, New Jersey 08731
. - - _ _ _ _ _ _ _ _ _ .._m__.m.__ ___ .m _
ENCLOSURE 1 OYSTER CREEK NUCLEAR GENERATING STATION E0CKET NO. 50-212 MEETING - JANUARY 6. J9jl ATTENDANCE L111 NRiE ORGANIZATISB A. W. Dromerick NRC/NRR/PD I-4 M. Banic NRC/NRR/EMCB William Koo HRC/NRR/DE/EMCB J. Zimerman NRC/NRR/PD I-4 Horace Shaw HRC/NRR/EMCB Robert A. McBrearty NRC/RI Ronald V. furia GPU Nuclear John Nakoski Resident Inspector, Oyster Creek M. M. Razzaque SRXB/NRR/NRC R. Nademus GPUN - NDE D. Slear GPUN - ERD D. Covill GPUN-NDE/ISI James Nestell MPR Associates Norman Cole MPR Associates David G. Jerko GPU Nuclear John Stolz NRC/NRR/PD I-4 R. Hermann NRC/NRR/EMCB
Oyster Creek Core Spray inspection I. Introduction Dave Slear i
- 11. Overview Dave Slear i A. Core Spray Description i
B. Observations / Video !
C. Results of Evaluations l
D. Conclusion / Status ,
Ill. Discussion l -
A. Past History Dave Slear :
l B. Evaluation.of 1992 Leak in inlet Dana Covil Pipe Coupling '
O. Mechanical Clamp Design Noman Cole I l
IV. Conclusions Dave Slear l-l l
l l
Date:
- January 6,1993
. 1 3
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- 11. Overview A. Core Spray Description
- Two-360'spargers with spray nozzles '
Two inlet nozzles,180' apart
- Inlet supply piping in annulus feeding spargers >
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t II. Overview l 1
B. Observations ,
- Air Test Results (= 2 to 3 psi Differential)
- Steady stream of air bubbles from System 1 pipe coupling
- Visual Of Both Systems 1 and 2
- Outline of what is going to be seen on tape:
A. Location of core spray system in vessel B. Description of core spray piping configuration .
C. Description of coupling where weld defect is located D. Core Spray System / Weld defect bubbling E. Close up of weld defect - blow-hole F. View of same weld in core spray system #2
- 3-
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9
- 11. Overview C. Results of Evaluations Welds Assessment
- Clearly visible defect in 1/4" field weld - =1/8" blow hole in weld on back side of coupling where access is limited (i.e., about 3" Clearence to Vessel)
- No sign of cracking - fatigue or IGSCC
- No other indication detected in remainder of weld a
System 2
- The back side of 1/4" field weld also indicates access created weld difficulties
- A linear indication in one area of weld, but judged "not service related" (e.g., two parallel weld passes)
- No other indication detected 4
e e
4 II. Overview C. Results of Evaluation (Continued)
Existing Weld Conditions Do Not Affect Core Spray System Operability >
+ Structural
- The blow hole defect in the 1/4" field weld is not a structural problem - the limiting weld is a 3/16" weld on a smaller diameter - approximately.7" of the circum-ference of the 1/4" weld can be missing and it still be equivalent to the limiting 3/16" weld
- Service loads are small; fatigue cracking of acceptable fillet weld unlikely
- 1/8" blow hole leakage is 1 to 3 gpm via annulus (see VG 8) l
- Still large flow margin
- Interpretation of environmental and stress conditions in conjunction with visual evidence leads us to believe IGSCC/ crevice corrosion is not present ;
- But if it were, crack growth over next cycle (2 years)-Is calculated to be less than = 3" and leakage through such an IGSCC would-be < .5 gpm which is still acceptable
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II. Overview D. Conclusion / Status Conclusions
- Best Judgement is That Leak Due To Weld Defect Due To 20+ Years Of Heatup And Cooldown
- Clamp Over The Joint is Not Needed And We Prefer Not To Install it, But Clamp And Tooling Design And Fabrication is Ongoing Status Clamp is Designed a
== 57' Long Tooling is Being Designed a
1st Clamp Delivery To OC 1/6 Refueling Complete 1/7 At 6 pm
- 2nd Clamp Delivery To OC 1/9
- Tooling Delivery To OC 1/8
- Clamp Installation ? Days 6-
I
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Ill. Discussion A. Past History 1978
- Crack Found in System II (Upper) Sparger, Confirmed By Air Test
- Root Cause - Likely IGSCC Driven By Initial Forming / Installation Residual Stress
- Redundant Mechanical Clamp installed
- No Cracks / Leaks Found in Supply Piping 1980 Additional Indications in Spargers, Added 7 Clamps To System 11 Sparger, 2 Clamps To System i Sparger
- No Leaks / indications in inlet Piping
- Subsequent Computer Enhancement of Observable Indications in Spargers Showed They Were Probably Not Cracks Post-1980 Performed 4 Air Tests, 5 Visual Inspections
- No Evidence Of Additional Leaks Or Indications Until 1992
+ 1992 Air Test Showed Leak In System l Coupling Field Weld 7
l 111. Discussion B. Evaluation Of 1992 Leak In inlet Pipe Coupilng
- 1. Applied Loads
- Normal Operation = D + FD + TO
- Shear strass in weld = 1.1 ksi (4.3 ksi w/ Selsmic)
- Fatigue for sound weld is negligible
- Shear stress in weld = 2.7 ksi (5.3 ksi w/ Seismic)
For Plastic Collapse Of Pipe, Crack Would Have To Extend 230 (14 Inches)
Nomenclature D = Deadweight FD = Drag Force P = Internal Pressure TO = Reactor Vessel, Core Shroud, and Core Spray Pipe at 550*F TA = Reactor Vessel and Core Shroud at 550'F and Core Spray Pipe at 300 F 6-
111. Discussion l B. Evaluation Of 1992 Leak in Inlet Pipe Coupling (Continued)
- 2. Crack Growth Based On IGSCC
- Initial size = 1/2"
- Residual stress = Sy
- Crack growth rate calculated in accordance with NUREG 0313
- At end of next cycle (2 years), crack could grow to 2" to 3"
- 3. Effect On Core Spray Flow Rate Flow Loss Through Leak is Not Significant
- 1/8" blow hole 1-3 gpm (observed condition)
- 3" x 1.5 mil crack < .5 gpm (from IGSCC)
Core Spray System Has Margin System I 500 gpm System ll 300 gpm 9
.- , ,. , - , n. -. .,
l11. DisCusslOn B. Evaluation Of 1992 Leak in inlet Pipe Coupling (Continued)
- 4. Defect inconsistent With IGSCC
- Visible Defect is Rounded, Clearly A Weld Fabrication Flaw
- High Bubbling Rate inconsistent With Air Flow From Tight IGSCC
- Pipe Internal Environment Was Stagnant And Deaerated.
Little Or No Oxygen Available For IGSCC.
- Highest Tensile Stresses As Well As Highest Oxygen Levels On Pipe OD. Expect IGSCC From OD And None is Observed.
- Best Judgement is That Leak is Due To Weld Defect Which Opened Up Through 20+ Years Of Heatups/Cooldowns, Although Some Corrosion-Assisted Defect Growth Cannot Be Ruled Out 10 1
s Ill. Discussion C. Mechanical Clamp Design Design Criteria
- Clamp Provides Same Structural Capability For Axlal Forces As Limiting 3/16" Shop Weld At The Coupling
- Clamp Components Machined From 300-Series Stainless Steel Plate /Bar Stock
- Clamp Meets Applicable Quality Assurance Program Requirements Clamp Design And Installation
- Clamp Designed And in Fabrication Clamp Installation Tooling Designed And in Fabrication
- Description Of Installation Sequence Assessment Of Clamp Effects
- Additional Deadweight / Seismic Forces On Annulus Piping Associated With The Clamp's Added Mass Are Acceptable
- Clamp Blocks Only A Very Small Amount Of Downcomer Flow Area - Has Negligible Effect On Recirculation Ratio
- Flow-induced Vibration Loads Associated With Clamp Are Negligible
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9 111. Discussion C. Mechanical Clamp Design (Continued)
Mock-Up Description
- Installation personnel training
- Installation tooling check-out
- Installation procedure verification Conclusions Regarding Clamps
- Clamp Provides Structural Capability Equivalent To The Coupling's 3/16" Shop Weld a Clamp Installation Effort is Significant
- Requires extensive tooling development and mock-up training of personnel
- Risks associated with potential for dropping clamp components during installation
t IV. Conclusions
- Observed Defect Likely An isolated Weld Defect
- No Evidence Of IGSCC Or On-going Corrosion
- No History Of IGSCC/ Crevice Corrosion in Thousands Of Other Fillet Welds At Oyster Creek Exposed To Similar Environment And Operating Pressure
- If IGSCC Does Occur, Consequences Are Acceptable For Next Operating Cyclo
- Mechanical Clamp Assembly Can Be installed (With Difficulty) And Will Reinforce Coupling
- Preferred Course of Action
- Do not install clamp at this time
- Monitor defect and rest of C/S system next outage
- Complete design, check-out of clamp installation tools, procedures for possible future use
- Best evidence indicates clamp not required
- Clamp will seriously complicate monitoring
- Should not add components to reactor internals unless clearly required
..